ML16043A389

Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis

ML16043A389
Person / Time
Site:	Palo Verde
Issue date:	02/18/2016
From:	Watford M Plant Licensing Branch IV
To:	Edington R Arizona Public Service Co
Margaret Watford, NRR/DORL
References
CAC MF7138, CAC MF7139, CAC MF7140
Download: ML16043A389 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2016 Mr. Randall K. Edington Executive Vice President Nuclear/

Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO INCORPORATE UPDATED CRITICALITY SAFETY ANALYSIS (CAC NOS.

MF7138, MF7139, AND MF7140)

Dear Mr. Edington:

By letter dated November 25, 2015, as supplemented by letter dated January 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15336A251 and ML16043A361), Arizona Public Service Company (APS, the licensee) submitted a license amendment request for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would modify technical specification (TS) requirements to incorporate the results of an updated criticality safety analysis for both new and spent fuel storage. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.

This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

R. Edington If you have any questions, please contact me at (301) 415-1233 or via e-mail at Margaret.Watford@nrc.gov.

Sincerely, 11

(}7l0cLt~ij Margaret M. Watfora, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530 cc: Distribution via Listserv

ML16043A389 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1 /LA NRR/DSS/SNPB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME MWatford JBurkhardt JDean* RPascarelli MWatford DATE 2/17/16 2/16/16 2/11/16 2/18/16 2/18/16